吴宜灿;王明煌;黄群英;赵柱民;胡丽琴;宋勇;蒋洁琼;李春京;龙鹏程;柏云清;刘超;周涛;金鸣;FDS团队;

• 1:中国科学院核能安全技术研究所
• 2:中国科学院中子输运理论与辐射安全重点实验室

摘要(Abstract)：

以铅或铅合金(统称铅基材料)为冷却剂的反应堆具有良好的中子学、热工水力学和安全特性,已成为第四代先进核能系统、加速器驱动次临界核能系统(ADS)以及聚变堆的主要候选堆型之一。本文简要介绍了先进核能系统发展趋势和铅基反应堆在核能发展中的地位,重点对铅基反应堆的发展历史与现状、铅基反应堆的基本特性以及铅基反应堆未来的发展前景进行了总结。

关键词(KeyWords)： 铅基反应堆;铅冷快中子反应堆;铅锂包层;铅铋合金

Abstract:

Keywords:

基金项目(Foundation): 国家自然科学基金(91026004);; 中国科学院战略性先导科技专项(XDA03040000、XDA03010100);; 国家磁约束核聚变能发展研究专项(2013GB108005、2015GB108005)

作者(Authors): 吴宜灿;王明煌;黄群英;赵柱民;胡丽琴;宋勇;蒋洁琼;李春京;龙鹏程;柏云清;刘超;周涛;金鸣;FDS团队;

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